Analysis of features of hydrodynamics and heat transfer in the fuel assembly of prospective sodium reactor with a high rate of reproduction in the uranium-plutonium fuel cycle

2016 ◽  
Vol 79 (8) ◽  
pp. 1315-1324
Author(s):  
A. S. Lubina ◽  
A. S. Subbotin ◽  
A. A. Sedov ◽  
A. A. Frolov
Keyword(s):  
Heat Transfer ◽  
Fuel Assembly ◽  
Fuel Cycle ◽  
High Rate ◽  
Uranium Plutonium ◽  
Plutonium Fuel

A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media

2019 ◽  
Vol 5 (4) ◽  
Author(s):  
Manish Kumar ◽  
Om Pal Singh
Keyword(s):  
Fast Neutron ◽  
Fuel Cycle ◽  
Fuel Burnup ◽  
Full Width ◽  
Half Maximum ◽  
Transient Time ◽  
Velocity Of Propagation ◽  
Neutron Leakage ◽  
Uranium Plutonium ◽  
Plutonium Fuel

A study of transverse buckling effect on the characteristics of nuclides burnup wave in multiplying media (cylindrical geometry) has been carried out. The burnup wave is characterized in terms of velocity of propagation, transient length (TL), and transient time (TT) in establishing the burnup wave and full width at half maximum (FWHM) in the established region of the wave. The uranium–plutonium fuel cycle is considered. The sensitivity of the results is studied for different radial buckling led leakage of neutrons. It is discovered that the velocity of the wave increases with the increase in the radius of the cylinder (i.e., reduction in the transverse buckling and hence increase in radial neutron leakage). FWHM is relatively insensitive to radial neutron leakage. The transient time and transient length are very large for smaller radius; these decrease with the increase in radius. The study provides insight on the build-up of burnup wave in the neutron multiplying media and brings out the importance of transverse buckling led radial neutron leakage on the characteristics of fuel burnup wave in multiplying media.

The Study of Typical PWR Nuclear Fuel Cycle

2014 ◽  
Vol 644-650 ◽  
pp. 5174-5178
Author(s):  
Yue Hong ◽  
Lan Lan Jiang ◽  
Dong Xiao Niu ◽  
Fu Yan Liu ◽  
Xiao Yu Wang ◽  
...  
Keyword(s):  
Sensitivity Analysis ◽  
Empirical Analysis ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Different Types ◽  
Uranium Plutonium ◽  
The One ◽  
Plutonium Fuel

This paper analyzed two different types of nuclear fuel cycle which refferred to one-through fuel cycle and close fuel cycle (uranium-plutonium fuel cycle). Based on specific economic elements related to each cycle process, this paper built a model to evaluate PWR nuclear fuel cycle’s economy. Then, for given data of PWR, empirical analysis and sensitivity analysis were carried out. The result showed the superiority of the close fuel cycle compared to the one-through cycle.

Uranium-Plutonium Fuel Cycle of a Fast Molten-Salt Reactor

Atomic Energy ◽  
2016 ◽  
Vol 121 (1) ◽  
pp. 63-69 ◽  
Author(s):  
L. I. Ponomarev ◽  
Yu. S. Fedorov ◽  
A. E. Miroslavov ◽  
A. M. Degtyarev
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Molten Salt Reactor ◽  
Uranium Plutonium ◽  
Plutonium Fuel

Problems of Assessing the Health Status of Personnel Working in Conditions of New Technologies for Nuclear Fuel Production

2021 ◽  
Vol 66 (3) ◽  
pp. 9-12
Author(s):  
A. Lyaginskaya ◽  
N. Shandala ◽  
E. Metlyaev ◽  
V. Kuptsov ◽  
O. Parinov
Keyword(s):  
Health Status ◽  
Nuclear Fuel ◽  
New Technologies ◽  
Circulatory System ◽  
High Morbidity ◽  
Length Of Service ◽  
Production Factors ◽  
Uranium Plutonium ◽  
The Many ◽  
Plutonium Fuel

Purpose: To identify the problem of assessing the health status of personnel working under the conditions of new technologies for the production of nuclear fuel. Material and method: The object of the research was the general morbidity of workers in the production of mixed nitride uranium-plutonium fuel (MNUP-fuel). The material for the study was the data presented in the «Health Passports». The paper used the method of comparative analysis of the overall morbidity of workers in the production of MNUP-fuel and workers in enterprises dealing with nuclear fuel. Results and analysis: At present, in our country, within the framework of the «Breakthrough» project, new technologies are being developed for the fabrication and refurbishment of mixed uranium-plutonium (MNUP) fuel. In the absence of radiation and hygienic standards for the content of fuel products in working rooms, in order to assess the influence of production factors, along with the radiation dose, the incidence of personnel is studied as an integral indicator of health. A study of the incidence of 50 workers in the production of MNUP fuel revealed: Relatively high incidence of general morbidity – 1122 diseases per 100 people or an average of 93.5 diseases per 100 people per year, regardless of the length of service. The leading diseases in the overall morbidity structure are diseases of the respiratory system – 26.0 % (1st place), eyes – 13.4 % (2nd place), musculoskeletal system – 11.4 % (3rd place), circulatory system – 10,9 % (4th place), injuries and poisoning – 8.4 % (5th place), digestive organs and genitourinary system – 7.7 % and 7.0 %, respectively (6th place), which make up 84.7 % of the total morbidity. Obviously, the effective dose of 4.6 mSv/year cannot be the only reason for the high morbidity in workers in complex radiochemical production, but characterizes only the influence of one of the many nonspecific factors of production. The existing system for assessing the health of personnel working in radiochemical production, in addition to analyzing the risks of deterministic and stochastic effects, should include an assessment of the overall morbidity of personnel.

2D Natural Convection and Radiation Heat Transfer Simulations of a PWR Fuel Assembly Within a Constant Temperature Support Structure

2006 ◽  
Author(s):  
Pablo E. Araya Go´mez ◽  
Miles Greiner
Keyword(s):  
Heat Transfer ◽  
Natural Convection ◽  
Fuel Assembly ◽  
Heat Generation ◽  
Temperature Difference ◽  
Wall Temperature ◽  
Radiation Heat Transfer ◽  
Radiation Heat ◽  
Fuel Rods ◽  
Water Reactor

Two-dimensional simulations of steady natural convection and radiation heat transfer for a 14×14 pressurized water reactor (PWR) spent nuclear fuel assembly within a square basket tube of a typical transport package were conducted using a commercial computational fluid dynamics package. The assembly is composed of 176 heat generating fuel rods and 5 larger guide tubes. The maximum cladding temperature was determined for a range of assembly heat generation rates and uniform basket wall temperatures, with both helium and nitrogen backfill gases. The results are compared with those from earlier simulations of a 7×7 boiling water reactor (BWR). Natural convection/radiation simulations exhibited measurably lower cladding temperatures only when nitrogen is the backfill gas and the wall temperature is below 100°C. The reduction in temperature is larger for the PWR assembly than it was for the BWR. For nitrogen backfill, a ten percent increase in the cladding emissivity (whose value is not well characterized) causes a 4.7% reduction in the maximum cladding to wall temperature difference in the PWR, compared to 4.3% in the BWR at a basket wall temperature of 400°C. Helium backfill exhibits reductions of 2.8% and 3.1% for PWR and BWR respectively. Simulations were performed in which each guide tube was replaced with four heat generating fuel rods, to give a homogeneous array. They show that the maximum cladding to wall temperature difference versus total heat generation within the assembly is not sensitive to this geometric variation.

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